Journal of the Korean Chemical Society (대한화학회지)

Korean Chemical Society (대한화학회)
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Cation Exchange Separation and Determination of Ruthenium in a Simulated Spent Nuclear Fuel

모의 사용후핵연료에 함유된 루테늄의 양이온교환 분리 및 정량

  • Suh, Moo-Yul (Nuclear Chemistry Research Team, Korea Atomic Energy Research Institute) ;
  • Sohn, Se-Chul (Nuclear Chemistry Research Team, Korea Atomic Energy Research Institute) ;
  • Lee, Chang-Heon (Nuclear Chemistry Research Team, Korea Atomic Energy Research Institute) ;
  • Choi, Kwang-Soon (Nuclear Chemistry Research Team, Korea Atomic Energy Research Institute) ;
  • Kim, Do-Yang (Nuclear Chemistry Research Team, Korea Atomic Energy Research Institute) ;
  • Park, Yeong-Jae (Nuclear Chemistry Research Team, Korea Atomic Energy Research Institute) ;
  • Park, Kyoung-Kyun (Nuclear Chemistry Research Team, Korea Atomic Energy Research Institute) ;
  • Jee, Kwang-Yong (Nuclear Chemistry Research Team, Korea Atomic Energy Research Institute) ;
  • Kim, Won-Ho (Nuclear Chemistry Research Team, Korea Atomic Energy Research Institute)
  • 서무열 (한국원자력연구소,원자력화학연구팀) ;
  • 손세철 (한국원자력연구소,원자력화학연구팀) ;
  • 이창헌 (한국원자력연구소,원자력화학연구팀) ;
  • 최광순 (한국원자력연구소,원자력화학연구팀) ;
  • 김도양 (한국원자력연구소,원자력화학연구팀) ;
  • 박영재 (한국원자력연구소,원자력화학연구팀) ;
  • 박경균 (한국원자력연구소,원자력화학연구팀) ;
  • 지광용 (한국원자력연구소,원자력화학연구팀) ;
  • 김원호 (한국원자력연구소,원자력화학연구팀)
  • Published : 20001200
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Abstract

Cation exchange separation and inductively coupled plasma atomic emission spectrometric(ICP-AES) determination of ruthenium in HCl solutions were studied to quantitatively determine ruthenium in spent nuclear fuels. Ruthenium-bearing samples were dissolved with the mixed acid solution(9 : 1 mole ratio, HCl-HNO$_3$) using an acid digestion bomb. Based on the absorption spectra and ion exchange behaviour of ruthenium in hydrochloric acid media, its possible chemical species were discussed. On a cation exchange column (0.7 ${\times}$ 8.0 cm) packed with AG 50W ${\times}$ 8(100~200 mesh) and equilibrated with 0.5 M HCl, ruthenium was eluated with 0.5 M HCl while uranium was retained on the column. The established separation method was applied to a simulated spent nuclear fuel and resulted in the recovery of 98.5% with a relative standard deviation of 0.7%.

사용후핵연료에 미량 함유되어 있는 루테늄 분석법을 개발하기 위하여 양이온교환법을 이용한 분리 조건을 조사하였다. 산분해 장치를 사용하여 9:1 몰비의 혼합산($HCl-HNO_3$)으로 루테늄 시료를 용해시켰다. 염산 용액에서 루테늄의 흡수스펙트럼과 이온교환 거동 조사를 통해 분리에 관련된 루테늄의 화학종을 제시하였다. 미량의 루테늄이 함유되어 있는 우라늄 용액을 양이온교환수지(AG 50W ${\times}$ 8, 100~200 mesh) 분리관(0.7 ${\times}$ 8.0 cm)에 넣고 0.5 M 염산으로 루테늄을 용리시켰다. 모의 사용후핵연료에 확립된 루테늄 분리방법을 적용하고 유도결합 플라스마 원자방출분광분석법으로 분석한 결과 루테늄 회수율은 98.5%이었다.

Keywords

References

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